Radiation Safety Information Computational Center
	Oak Ridge National Laboratory Post Office Box 2008 Oak Ridge, Tennessee 37831-6362 Managed by UT-Battelle, LLC for the U.S. Department of Energy under contract DE-AC05-00OR22725 Phone No. 865-574-6176 FAX 865-574-6182 Internet: PDC@ORNL.GOV http://www-rsicc.ornl.gov/rsicc.html
No. 457	March 2003
"It is the growling man who lives a dog's life" - Coleman Cox

• 40 Years Ago - This is How it Was!
• Oak Ridge National Laboratory is 60!
• Change to the Computer Code and Data Collection
• CCC-711/EASY 99
• Monthly Code Focus
• CONFERENCES, COURSES, SYMPOSIA
• Condensed Table of Conferences
• Advances in Nuclear Fuel Management III - Call For Papers
• 2003 IEEE Nuclear and Space Radiation Effects Conference (NSREC)
• International Conference on Radiation Shielding (ICRS-10) and Topical Meeting on Radiation Protection & Shielding (RPS 2004)
• 2003 International Congress on Advanced Nuclear Power Plants (ICAPP '03)
• 6th International Symposium on ESR Dosimetry and Applications
• 7th International Conference on Nuclear Criticality Safety (ICNC2003)
• 9th International Conference on Environmental Remediation and Radioactive Waste Management
• 21st International System Safety Conference
• 9th International Symposium in Radiation Physics (ISRP-9)
• M&C 2003
• MCNP Courses for 2003
• MCNP Visual Editor Classes
• MCNPX Workshops for 2003
• Workshop on Nuclear Data for the Transmutation of Nuclear Waste
• Practical MCNP for the HP, Medical Physicist, and Rad Engineer
• Radiation Process Simulation and Modeling User Group
• SAMMY WORKSHOP
• SCALE 5 Plus Workshop
• Supercomputing in Nuclear Applications
• CALENDAR
• ACCESSION OF NUCLEAR SYSTEMS LITERATURE

RSIC published its first newsletter June 1, 1963. The newsletter announced the establishment of the center, described its program and services, and requested shielding information. A Board of Volunteer Coordinators was listed in the newsletter: 47 scientists and engineers who represented a cross section of the international shielding community. RSIC staff met with the Coordinators for the first time at the 1963 summer meeting of the American Nuclear Society in Salt Lake City, Utah. Groundwork was laid for cooperation throughout the nuclear industry. It was not until January 1965 that the second newsletter was published, and that was due to pressure from the Coordinators! It was published on a monthly basis thereafter.*

RSICC's 40th anniversary will be formally acknowledged at a dinner on Tuesday, April 8th at the M&C Topical Meeting in Gatlinburg, Tennessee. Among the speakers will be Betty Maskewitz and Dr. Alvin Weinberg.
 

*Betty F. Maskewitz, History of the Engineering Physics and Mathematics Division 1955-1993, p. 25, Oak Ridge National Laboratory Report ORNL/M-2998 (June 2001).
 
 

Oak Ridge National Laboratory celebrated its 60th anniversary with a series of events and activities to help preserve the lab's history, thank the community and honor ORNL's past and present staff.

In February 1943, construction began at ORNL (called Clinton Laboratories until 1948) on what became the world's first continuously operated nuclear reactor. The Graphite Reactor began operation in November 1943 and demonstrated that a reactor could provide a sustained nuclear reaction and produce significant amounts of plutonium. Some 20 months later, plutonium produced in Hanford, Wash., was used in one of the atomic bombs that accelerated the end of World War II.

Since its early years, ORNL's mission has changed from weapons research to one that includes world-class research in energy, neutron science, biological systems, advanced materials, national security and high-performance computing.

ORNL Director Bill Madia said the laboratory's celebration was designed with three goals. "We are making sure future generations know about the tremendous contributions of those who worked here before us. We are thanking the community for their help and support over the years. And we are recognizing the wonderful staff, past and present, who have made ORNL a world leader in scientific research."

Dozens of ORNL retirees, including some of the original staff from 1943, heard presentations that recounted the research in the early years of the laboratory and life in the Secret City during the war years.

The ORNL staff has organized several initiatives to chronicle and preserve the laboratory's history. Approximately 25 ORNL retirees are being interviewed on camera to develop an oral history of the laboratory's first two decades. An ORNL history room has been established for the identification, preservation and display of artifacts related to the science and life of early ORNL staff. ORNL also has renovated and upgraded the exhibit wing of the Graphite Reactor to display both the history and future of the laboratory's scientific agenda.

A commemorative 60th anniversary stamp and postal cover will be unveiled at the American Museum of Science and History in Oak Ridge (http://www.amse.org/). Collectors may purchase the stamp at the museum.

Madia said the anniversary will continue throughout 2003 with other events and projects that will celebrate both the past and future of ORNL.

One new version of a package was added to the computer code collection this month.
 

CCC-711/EASY 99
OP SYS: Windows & Unix
Language; Fortran 77
Computers: PC & Workstations
Format: Windows & tar

UKAEA/EURATOM Fusion Association, Oxfordshire, United Kingdom, through the OECD NEA Data Bank, Issy-les-Moulineaux, France, contributed a Windows version of this multipurpose activation and transmutation code system. EASY-99 is an updated version of CCC-678/EASY-97. Information on EASY-99 is posted at the UKAEA web site: http://www.fusion.org.uk/. The European Activation System (EASY) is a complete tool for the calculation of activation in materials exposed to neutrons. It can be used for any application (fusion, transmutation, fission and accelerator) where the neutron energy does not exceed 20 MeV. EASY-99 consists of the inventory code FISPACT-99 and the EAF-99 file, which contains various libraries of nuclear data. EASY-99 calculates the response of materials irradiated in a neutron flux. It is designed to investigate fusion devices which will act as intense sources of high energy (14 MeV) neutrons and cause significant activation of the surrounding materials. The EAF-99 library contains 12468 excitations functions involving 766 targets from 1H to 257Fm, in the incident energy range up to 20 MeV.

Fortran and C compilers are required to build executables on Unix or Linux. Makefiles are provided for Sun, IBM, HP and Intel PC Linux systems. The Windows release was developed for Windows 95, 98 and NT4.0 in 1999. The included PC executable created by the author with the Salford FTN77 compiler was tested at RSICC on Pentium computers running WindowsNT, Windows2000 and WindowsXP. Fortran source files are not included in the Windows distribution. The package is transmitted on a CD-ROM and contains scripts, source files, test cases, data libraries, a Windows executable and documentation files. References: UKAEA FUS 407 (December 1998), UKAEA FUS 408 (December 1998), UKAEA FUS 409 (December 1998), UKAEA FUS 410 (December 1998), EDS-0 (December 1998), EDS-3a., EDS-2a (December 1998). Fortran 77 & C; IBM RS/6000, SUN, HP, Linux PC (C00711MNYCP01).

As years have gone by many different codes and applications have been sent to RSICC for stewardship. We currently have over 1700 analytical code and data packages and distribute as many each year to 73 countries in the world. To help 'categorize' each package, we have developed a database of 'Subject Categories' to attach applications to the packages at RSICC. Doing so requires investigation into each code package, user feedback from end use statements, and extensive RSICC staff experience and analysis so that we can deliver useful information each month on the 30 different categories we have identified thus far. Links to the package abstracts are embedded into the WWW version of the RSICC Newsletter. Feedback from our Newsletter community is very valuable so please direct your comments and/or suggestions to PDC@ORNL.GOV. Many packages in the RSICC code collection are in this subject category. A few are highlighted here for your review of Radiation Protection and Shielding.

ANISN-ORNL
DANTSYS
DOORS 3.2
HIMAC
ISO-PC 2.1
MCNP4C2
PARTISN 2.99
QAD-CGGP-A
RSAC-6
SCALE 4.4A
SUGGEL
TART2000

RSICC attempts to keep its users/contributors advised of conferences, courses, and symposia in the field of radiation protection, transport, and shielding through this section of the newsletter. Should you be involved in the planning/organization of such events, feel free to send your announcements and calls for papers via email to FINCHSY@ornl.gov with "conferences" in the subject line by the 20th of each month. Please include the announcement in its native format as an attachment to the message. If the meeting is on a website, please include the url.

Every attempt is made to ensure that the links provided in the Conference and Calendar sections of this newsletter are correct and live. However, the very nature of the web creates the possibility that the links may become unavailable. In that case, please call or mail the contact provided. Below is a condensed list of the conferences only. More details are listed following the table.
 
 

Preparations for the American Nuclear Society's Advances in Nuclear Fuel Management III Topical Meeting to be held in Hilton Head Island, South Carolina, during the period of October 5-8, 2003, have now begun in earnest. You are invited to serve on the Meeting's Technical Program Committee (TPC). In this capacity your commitment will include:

1. Electronically submit one or more papers, and encourage colleagues to do the same,
2. Help identify and organize special session(s) on timely topics you are interested in, and solicit participation, and
3. Electronically review papers assigned to you in a timely and professional manner

Please return the following information (name, affiliation, phone, alternative email if preferable, topics of interest) to Youssef A. Shatilla at shatilya@westinghouse.com.

The success of this meeting depends on your active support and involvement. Finally, please bookmark the conference web site: http://rpd.ans.org/nfm.htm and visit it occasionally for news and updates. Comments and suggestions are most welcome.
 
 

The 2003 IEEE Nuclear and Space Radiation Effects Conference (NSREC) will be held in Monterey, California, July 21-25, 2003. This annual meeting of engineers and scientists presents the latest techniques for enhancing the performance of microelectronic devices and circuits that are used in radiation environments. The final call for papers for the 2003 IEEE Nuclear and Space Radiation Effects Conference (NSREC) is available on the web site at www.nsrec.com. Deadline for submission is February 7, 2003.

Make plans for the 2003 short course in Monterey. Joe Benedetto and his team of professors have put together an interesting program about radiation effects on device scaling. The syllabus is at www.nsrec.com/short.htm.

Forms to nominate an outstanding colleague for the 2003 Radiation Effects Award are at www.nsrec.com/nominate.htm. This award comes with a handsome IEEE plaque and $2000 check.

University professors - Forms are available on the NSREC web site to nominate an outstanding student for the 2003 IEEE NPSS Phelps Continuing Education Grant. The cash award ($500 - $1000) comes with an IEEE certificate and complimentary short course registration. NSREC plans to award two grants this year. See www.nsrec.com/steering.htm.

Keep checking the web site at www.nsrec.com for the latest NSREC information. Contact Paul Dodd, Sandia National Laboratories, 505-844-1447 if you have questions.
 
 

The Tenth International Conference on Radiation Shielding (ICRS-10) and the Thirteenth Topical Meeting of the Radiation Protection and Shielding Division of the American Nuclear Society (RPS 2004) will be held May 9-14, 2004.

The Local Organization has been assigned to ITN (the Nuclear and Technological Institute, in Lisbon), a laboratory of the Portuguese Ministry of Science and Higher Education. At the international level, the joint organization is co-sponsored by The Nuclear Energy Agency (NEA) of the Organization for Economic Co-operation and Development (OECD), The Radiation Protection and Shielding Division (RPSD) of the American Nuclear Society (ANS), and The Radiation Safety Information Computational Center (RSICC, Oak Ridge National Laboratory).

It is anticipated that this will be the most important event in the areas of Radiation Shielding and Radiation Protection during 2004. For further information please refer to the Conferences Web pages at the following URL http://www.itn.mces.pt/ICRS-RPS. Please don´t hesitate to contact the Conference Secretariat at icrs-rps@itn.mces.pt.

In addition, if you would be interested in serving on the Scientific Program Committee, and contribute to the success of the meeting by either submitting or encouraging colleagues to submit papers, and participating in the technical review process, please contact the Conference Secratariat at the above email and provide your name, organization, email and topics of interest or expertise.

The Organizing Committee welcomes your comments and suggestions to make your meeting a success.
 
 

We are pleased to announce the call for papers for the "2003 International Congress on Advanced Nuclear Power Plants" (ICAPP '03) which will be held in Cordoba, Spain, May 4-7, 2003, at the Congress Palais. Please make note of the October 15, 2002 deadline for abstracts.

Following the highly successful ICAPP '02 meeting held in Hollywood, Florida, this international congress will bring together international experts of the nuclear industry involved in the operation, development, building, regulation, and research related to nuclear power plants. The conference is sponsored by the leading nuclear societies of Europe, Asia, and the USA.

The program will cover the full spectrum of nuclear power plant issues from design, deployment and construction of plants to research and development of future designs and advanced systems. The program is expected to cover lessons learned from power, research and demonstration reactors from over 50 years of experience with operation and maintenance, structures, materials, technical specifications, human factors, system design, and reliability. You may visit the ICAPP '03 website at www.ans.org/goto/ icapp03 for updated information on the congress and to download a copy of the Call For Papers.
 
 

The 6th International Symposium on ESR Dosimetry and Applications will be held October 12-16, 2003, in Campos do Jordão, Brazil. For complete information, please see http://www.if.usp.br/ VI_ESR_2003/ and click on "second announcement (PDF version)" on the left side of the screen.
 
 

The 7th International Conference on Nuclear Criticality Safety (ICNC2003) will be held October 20-24, 2003, in Tokai-mura, Japan. This conference has been held approximately every 4 years under the support of OECD/Nuclear Energy Agency/Nuclear Science Committee. The last conference, hosted by Japan, was the 3rd conference held in Tokyo in 1987. In the Versailles conference held in 1999, over 300 people from 25 countries participated, and more than 200 presentations were given on the recent activities in research work, industrial applications, regulatory studies, and other topics related to criticality safety. ICNC2003 will provide a good opportunity for communication among researchers, engineers, plant operators, and regulators. The Conference will consist of invited talks, contributed talks, and poster sessions. On the final day of the conference, technical tours to nuclear facilities are scheduled, and social programs are planned during conference. Please see the website for more information: http://www.icnc.jp/.
 
 

The conference will be held in Oxford, England, September 21-25, 2003. Session M-6 - Applying Strategic Planning, Decision-making, and Risk Reduction Methodologies in EM, includes the following:

-- Applications of strategic planning, decision-making, and/or risk reduction methodologies and tools (e.g., roadmapping) to resolve environmental management issues

-- Innovative approaches to decision-making to resolve problems/issues related to environmental management

-- Innovative approaches to assessing risk and cost-effective reduction of risk for issues related to environmental management

-- Innovative approaches to strategically plan for and implement science and technology (S&T) to resolve environmental barriers to project completion

-- Ways to effectively integrate strategic planning, decision-making, and risk reduction techniques and tools to resolve environmental management issues

-- Methodologies used in developing the sites' plans to meet DOE EM's goals of site closures, cost savings, schedule acceleration, and risk reduction

Additional details on the ICEM conference are on the website at http://www.icemconf.com.
 
 

The System Safety Society is pleased to announce the 21st International System Safety Conference, August 4-8, 2003, in Ottawa, Ontario, Canada. The conference is an international forum for the technical presentation and discussion of all aspects and issues regarding system safety engineering and management. The conference theme is "Broader Perspectives, Focused Solutions." The emphasis is on the knowledge and skills necessary to create system safety solutions for increasingly complex technologies and missions. The range of topics will cover both the art and science of system safety and the organizational issues influencing the effective management of system safety in the product life cycle. This is the major conference for system safety and related professions, with a week of technical sessions, tutorials, workshops, special events, social affairs, luncheons, and the society's awards banquet. The conference proceedings are the premier collection of work in the system safety field. For more information, please visit: http://www.russona.com/issc21/.
 
 

The 9th International Symposium on Radiation Physics (ISRP-9) will be held in Cape Town, South Africa, October 27-31, 2003. This triennial event will be organized jointly by the International Radiation Physics Society ( IRPS ) and iThemba Laboratory for Accelerator Based Sciences ( iThemba LABS) [formerly the National Accelerator Centre]. The Symposium is the latest in a series which began in Calcutta in 1974 and thereafter continued in Penang (1982), Ferrara (1985), São Paulo (1988), Dubrovnik (1991), Rabat (1994), Jaipur (1997) and Prague (2000). A 2½ day "Workshop on Radiation-Based Analytical Techniques" (WoRBAT) will be held prior to ISRP-9 (October 24-26, 2003) with emphasis on x-ray fluorescence and diffraction (XRF, XRD) and particle-induced x-ray emission (PIXE). For more information, please visit www.medrad.tlabs.ac.za/isrp9.htm.
 
 

The American Nuclear Society's Mathematics and Computation Topical Meeting, M&C 2003, will be held in Gatlinburg, Tennessee, April 6-10, 2003. The unique setup for this conference, entitled "Nuclear Mathematical and Computational Sciences: A Century in Review, A Century Anew," promises to provide an exciting and unprecedented opportunity for students and professionals in the field to learn about its rich intellectual heritage from leading figures. The Review section of the conference is comprised of eight lectures on selected topics of common interest to the membership of the Mathematics and Computation Division, the primary sponsor of the meeting. The Anew section of the meeting will include contributed and invited papers on standard topics in this series of conferences. Please refer to the conference web site http://meetingsandconferences.com/MC2003/ for details on the lecture series and lecturers, a list of topics for contributed papers and special sessions, author instructions, and general information about the conference.

The web site for M&C 2003 is now open for submitting papers. Please check the "Call for Papers" link to learn about the topics of interest in this conference, including special session topics. The "Authors" link has templates for preparing full papers in MS Word, WordPerfect, and LaTeX. Please note that abstract submission is not required due to the Math & Computational Sciences Division's policy of reviewing only full papers for inclusion in meetings where the division is the primary sponsor. We look forward to welcoming you to Gatlinburg.
 
 

Registration: http://www-xdiv.lanl.gov/x5/MCNP/registration.html
MCNP home page: http://www-xdiv.lanl.gov/x5/MCNP/index.html
LANL contact: selcow@lanl.gov
European contact: sartori@nea.fr
Japanese contact: tadakazu@hero.tokai.jaeri.go.jp

The introductory class is for people who have little or no experience with MCNP. The intermediate to advanced class will be held for people who have used MCNP and want to extend their knowledge and understanding of the code system.

The classes will be based on MCNP5. The code and data package will be available through RSICC at a reduced rate to class participants. The new capabilities of version 5 will be covered.

The other capabilities on MCNP will also be covered, including: basic and advanced geometry, source definitions, tallies, data, variance reduction, statistical analysis, criticality, plotting of geometry, and particle tracks, neutron/photon/electron physics.

All classes provide interactive computer instruction. Time will be available to discuss individual questions and problems with MCNP experts or to pursue in more detail topics mentioned in the talks.

Please note that other classes are offered based on MCNP. The classes mentioned here are the only ones that are taught by the people who develop and write MCNP.
 
 

The Visual Editor is a powerful visualization tool that can be used to rapidly create complex Monte Carlo N Particle (MCNP 4C2) geometry models, including lattices, universes, fills, and other geometrical transformations. The Visual Editor can:

Display MCNP 4C2 geometries in multiple plot windows,
Create surfaces and cells to build a geometry,
Create materials using the local xsdir file,
Store commonly used materials in a material library,
Sub-divide large cells into smaller cells,
Create cells containing universes and lattices,
Interactively set cell importances from the plot window, and
Display source points and collision points in the plot window.

Two classes are scheduled June 2-6, 2003, and September 8-12, 2003, both in Richland, Washington. The class will focus on the use of the visual editor, with an overview of MCNP. The fifth day is optional and will focus on using the Visual Editor and MCNP to do some example problems.

Class will include computer demonstrations and exercises that will focus on creating and interrogating input files with the Visual Editor. Advanced visualization work using MCNP will also be demonstrated. The class will be taught on Pentium computers running the Linux operating system and Windows NT. Class attendees can use either the Linux or Windows version of the visual editor. Attendees are encouraged to bring their own input files for viewing and modifying in the visual editor. Further information on this class can be located at: http://www.mcnpvised.com/train.html, or by contacting Randy Schwarz (email randyschwarz@mcnpvised.com).

On April 6, 2003, there is a four hour class that is being held in conjunction with MC 2003. The class will be held Sunday and will cover the most popular features of the Visual Editor, including viewing files, creating simple geometries and setting importances. For more info on the MC2003 conference, see http://meetingsandconferences.com/MC2003.
 
 

Lead Teachers: Drs. John Hendricks, Gregg McKinney, Laurie Waters
Organizer: HQC Professional Services Contact: bill@solutionsbyhqc.com
More Information: http://mcnpxworkshops.com MCNPX homepage: http://mcnpx.lanl.gov

MCNPX is the LANL all-particle, all-energy (eV-TeV) Monte Carlo transport code based on MCNP4C, LAHET, CEM, etc. MCNPX has been in active development since 1995, sponsored by the particle accelerator community. It has now become an accepted tool for a broad range of applications by nuclear engineers, physicists, and scientists. The MCNPX development effort has expanded the use of the Los Alamos tools to applications such as APT, waste transmutation, accelerator shielding and health physics, particle beam cancer therapy, space shielding and cosmic ray analysis, single event effects in semiconductors, radiography, and more detailed analysis of the effects of light and heavy ions in matter. In addition, the entire functionality of MCNP4C is retained. New variance reduction and data analysis techniques, many adapted from high energy accelerator methodologies, have also been added, such as the extensive 'mesh tally' capability which allows up to 3-d plotting of particle tracks, fluence and fluence-derived quantities, energy deposition, next event estimator generation contributions and particle sources.

The workshops include hands-on instruction, generally on PC Windows machines. Subject to participant export approval for the MCNPX beta test team, participants will be able to access the Fortran-90 version of MCNPX 2.4, the LA150 (150 MeV) cross-section data for over 40 isotopes for incident neutrons and protons, and 12 for photonuclear interactions, and a notebook of viewgraphs. Follow-up consultation for class participants will be provided.

Classes are taught by experienced MCNPX code developers and instructors. More information on code versions and capabilities is available at MCNPX Workshops web site http://mcnpxworkshops .com.
 
 

The "Workshop on Nuclear Data for the Transmutation of Nuclear Waste" will be held September 1-5, 2003, at GSI-Darmstadt, Germany. The workshop is organized on the occasion of the end of the HINDAS research program, a collaboration of several European Institutes working on the subject of "High and Intermediate Nuclear Data for Accelerator Driven Systems." Please note that the topics included in the workshop are not restricted to the HINDAS research program. All contributions to the subject of the workshop are more than welcome.

The workshop time-schedule will be organized in the following way: Monday will be dedicated to a closed HINDAS meeting. On Tuesday, the open sessions will start and last till the end of the workshop on Friday.

Those who are interested in participating in the workshop are invited to register (no fee) before August 1, 2003, using the workshop website http://www-wnt.gsi.de/tramu. There is also information on workshop topics, accommodations, transportation, and key dates. Please contact Aleksandra Kelic, A.Kelic@gsi.de if you have questions.
 
 

DATE: June 16-20, 2003 (4.5 days)
FEE: $1,450 per person
PLACE: The MESA Complex, Room 130, University of New Mexico-Los Alamos Campus

Monte Carlo type calculations are ideally suited to solving a variety of problems in radiation protection and dosimetry. This course is aimed at the HP, medical physicist, and rad engineer with no prior experience with Monte Carlo techniques. The focus is almost entirely on the application of MCNP™ to solve a variety of practical problems in radiation shielding and dosimetry. The intent is to "jump start" the student toward using MCNP™ productively. Extensive interactive practice sessions are conducted on a personal computer. Topics will include overview of the MCNP™ code and the Monte Carlo method, basic concepts, input file preparation, geometry, source definition, standard MCNP tallies, interpretation of the output file, exposure and dose rate calculations, radiation shielding, photon skyshine, detector simulation and dosimetry. Students will be provided with a comprehensive class manual and a diskette containing all of the practice problems. This course has been granted 32 Continuing Education Credits by the AAHP, and 4.5 CM points by the American Board of Industrial Hygiene.

The course is offered by the Health Physics Measurements Group at the Los Alamos National Laboratory and is co-sponsored by RSICC. Registration is available online at http://drambuie.lanl.gov/ ~esh4 mcnp.htm. Make checks payable to the University of California (checks must be in U.S. dollars on a U.S. bank) and mail together with name, address, and phone number to: Los Alamos National Laboratory, Group HSR-4, MCNP Class/David Seagraves, Mail Stop J573, Los Alamos, NM 87545.

This course is offered by the Health Physics Measurements Group at LANL and is a completely separate offering from the other courses offered by other groups at Los Alamos.

Inquiries regarding registration and class space availability should be made to David Seagraves, 505-667-4959, fax: 505-665-7686, e-mail: dseagraves@lanl.gov. Technical questions may also be directed to Dick Olsher, 505-667-3364, e-mail: dick@lanl.gov.
 
 

The Radiation Process Simulation and Modeling User Group (RPSMUG) announces its annual meeting to be held April 22-23, 2003, at the National Institute of Standards and Technology in Gaithersburg, Maryland. The meeting will consist of technical presentations, round-table discussions and informational sessions related to the use of mathematical models and simulation in radiation processing (gamma, electron beam, and x-ray). New RPSMUG officers will be installed at this time. Please click on announcement for more information.
 
 

RSICC is pleased to announce that a five-day workshop on Oak Ridge National Laboratory's (ORNL) SAMMY code will be held May 12-16, 2003, in Knoxville, Tennessee. This training course is intended for those who are interested in the theory of neutron cross sections in the resonance region, and in the use of SAMMY for the analysis of experimental neutron-induced cross-section data for extracting values and covariances for resonance parameters. Both novice and experienced SAMMY users would benefit from the intensive and extensive examination of all aspects of resonance parameter analyses.

During the workshop, lectures and computer applications will alternate. Lectures will include both theoretical discussion and practical examples for each topic. The lecturer is Dr. Nancy Larson of the Nuclear Data and Information Analysis Group, Nuclear Science and Technology Division of ORNL, author of the SAMMY code.

Topics include (but are not limited to) the following:

I. R-matrix formalisms (both resolved and unresolved resonance region)

II. Simulation of experimental conditions
     A. Multiple nuclides in the sample
     B. Doppler- and resolution-broadening
     C. Self-shielding and multiple-scattering corrections
     D. Other data-reduction effects

III. Mathematical methods used for experimental data-fitting
     A. Use of covariance information

IV. Reporting results for Evaluated Nuclear Data Files

V. Features in the latest version of the analysis code SAMMY

The workshop will include hands-on computer applications using the latest version of SAMMY (M6). Computer exercises will lead participants through the various features of the code beginning with simple examples and leading to realistic situations. Participants who are experienced SAMMY users are encouraged to bring their own examples as well.

The number of PC workplaces available at the training center restricts the number of workshop participants accepted. Therefore, we encourage you to register as early as possible. The SAMMY workshop web site with further detailed information and on-line registration can be accessed at http://www-rsicc.ornl.gov/SAMMY/intro.html). Please bookmark the site and visit it occasionally for news and updates as they become available.
 
 

Version 5 of the SCALE software system is scheduled for release in 2003. This half-day tutorial workshop will highlight significant new computational capabilities in SCALE 5 plus current developments that will appear in later SCALE releases. The workshop at the conference hotel in Gatlinburg on Thursday afternoon April 10, 2003, will be part of the American Nuclear Society M&C 2003 Topical Meeting in Gatlinburg, Tennessee. The workshop will be hosted by Oak Ridge National Laboratory, immediately following the final technical sessions of the topical meeting.

The workshop will feature presentations on the following new computational capabilities to be released in SCALE 5:

· SEN3 3-D sensitivity/uncertainty sequence (using KENO V.a)
· TRITON/NEWT 2-D flexible mesh discrete ordinates automated sequences for criticality safety and depletion/source term analyses.
· New resonance cross-section processing capabilities using continuous energy and ENDF/B-VI cross sections.
· New 2-D interactive plotting of KENO and XSDRNPM results with Javapeno.

Plus, the workshop will also feature presentations on the following developments planned for release:

· Continuous energy version of the KENO V.a criticality safety code
· 3-D automated variance reduction for Monte Carlo radiation shielding analysis

The registration fee is $200. You can register online at www.ornl.gov/scale/register_scale5.html or as part of your M&C 2003 registration.
 
 

The conference on "Supercomputing in Nuclear Applications" SNA-2003, will be held in Paris, September 22-24, 2003.

The web pages (http://sna-2003.cea.fr/) were expanded to include information on tours, sightseeing and events scheduled at the time of the conference.

One of the events at SNA-2003 is linked to the museum of "arts et metier", literally of arts & crafts; art is here used in its primary meaning: skills acquired through studies and by practice, technical knowledge. In this museum are displayed among many other items the "supercomputer" of 1642: arithmetical machine by Blaise Pascal, the original pendulum of Foucault (1851) or the instrument he developed to measure the speed of light (1852), or a decimal clock with a day of 10 hours each of 100 minutes and a minute of 100 seconds etc.
 
 

March 2003

14th Annual U.S. Hydrogen Meeting, Mar. 4-6, 2003, Washington, DC. Contact: Catherine E. Grégoire Padró (tel 303-275-2919, fax 303-275-2905, email owner-hydrogen@mail.nrel.gov, url http://www.hydrogenconference.org/).

MCNP Course, Mar. 11-14, 2003, North Carolina State University. Contact: Elizabeth Selcow (email selcow@lanl.gov, url http://www-xdiv.lanl.gov/x5/ MCNP/index.html).

MCNP Course, Mar. 24-28, 2003, London, Contact: Elizabeth Selcow (email selcow@lanl.gov, url http://www-xdiv.lanl.gov/x5/ MCNP/index.html).

Software Quality Forum 2003, Mar. 24-27, 2003, in Arlington, VA. Contact: Kathleen Canal (email kathleen.canal@hq.doe.gov, url http://cio.doe.gov/sqas).

MCNPX Advanced Workshop, Mar. 31-Apr. 4, 2003, Knoxville, TN. Contact: Bill Hamilton (tel 505-455-0312, email registrar@mcnpxworkshops.com url http://mcnpxworkshops.com for details).

April 2003

ANS Topical Meeting, Nuclear Mathematical and Computational Sciences: A Century in Review, A Century Anew, Apr. 6-10, 2003, Gatlinburg, TN. Co-sponsored by the American Nuclear Society's Reactor Physics, and Radiation Protection and Shielding Divisions, as well as the ANS Oak Ridge/Knoxville Local Section, Oak Ridge National Laboratory's Radiation Safety Information Computational Center, the Nuclear Energy Agency of the OECD, the Korean Nuclear Society, and the Canadian Nuclear Society. Contacts: Yousry Azmy (tel 814-865-0039, email yya3@psu.edu or Bernadette Kirk (tel 865-74-6176, email kirkbl@ornl.gov, url http://meetingsandconferences.com /MC2003/index.html).

Visual Editor for MCNP, Apr. 6, 2003, Gatlinburg, TN. Contact: Randy Schwartz (url http://www.mcnpvised.com/ved/class7. html).

MCNP Course, Apr. 11, 2003, Gatlinburg, Tennessee. Contact: Elizabeth Selcow (email selcow@lanl.gov, url http://www-xdiv.lanl.gov/x5/ MCNP/index.html).

39th NCRP Meeting, Apr. 9-10, 2003, Arlington, VA. Contact: William Beckner (tel 301-657-2652, fax 301-907-8768, url http://www.ncrp.com).

Radiation Process Simulation and Modeling User Group, Apr. 22-23, 2003, Gaithersburg, MD. Contact: Mark Smith (tel 704-587- 8914, email msmith@iba-group.com).

SCALE5 Workshop, Apr. 28-May 2, 2003, Oak Ridge, TN. Contact: Kay Lichtenwalter (email x4s@ornl.gov, scalehelp@ornl.gov, url http://www.ornl.gov/scale/ workshop_mc2003.html).

May 2003

Radiation Transport Calculations using the EGS Monte Carlo System, May 5-8, 2003, Ottawa, Canada. Contact: Blake Walters, Ionizing Radiation Standards, National Research Council of Canada, Ottawa, Canada, K1A 0R6. (tel 613-993-2715, fax 613-952-9865, email bwalters@irs.phy.nrc.ca, url http://www.irs.inms.nrc.ca/inms/irs/papers/egsnrc/brochure.html).

MCNP Course, May 12-16, 2003, Japan. Contact: Elizabeth Selcow (email selcow@lanl.gov, url http://www-xdiv.lanl.gov/x5/MCNP/ index.html).

MCNPX Introductory Workshop, May 19-23, 2003, Los Alamos/Santa Fe, NM. Contact: Bill Hamilton (tel 505-445-0312, email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com for details).

June 2003

Visual Editor for MCNP, June 2-6, 2003, Richland, Washington. Contact: Randy Schwarz (email randyschwarz@mcnpvised.com, url http://www.mcnpvised.com/ train.html).

Practical MCNP For The HP, Medical Physicist, And Rad Engineer, June 16-20, 2003, Los Alamos, NM. Contact: David Seagraves (tel 505-667-4959, fax 505-665-7686, email dseagraves@lanl.gov, url drambuie.lanl.gov/~esh4/mcnp.htm).

MCNP Course, June 2003, (TBA), Los Alamos National Laboratory, Los Alamos, NM. Contact: Elizabeth Selcow (email selcow@lanl.gov, url http://www-xdiv.lanl.gov/x5/MCNP/index.html).

MCNPX Advanced Workshop, June/July (tbd), 2003, Europe. Contact: Bill Hamilton (tel 505-455-0312, email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com for details).

July 2003

Intercomparison on the Usage of Computational Codes in Radiation Dosimetry, July 14-16, 2003, Bologna, Italy. Contact: Gianfranco Gualdrini (tel 39-051-6098350, fax 39-051-6098003, email guald@bologna.enea.it, url http://www.nea.fr/ download/quados/quados.html).

2003 IEEE Nuclear and Space Radiation Effects Conference (NSREC), July 21-25, 2003, Monterey, CA. Contact: Paul Dodd (tel 505-844-1447, url http://www.nsrec.com).

MCNPX Advanced Workshop, June/July (tbd), 2003, Europe. Contact: Bill Hamilton (tel 505-455-0312, email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com for details).

August 2003

21st International System Safety Conference, Aug. 4-8, 2003, Ottawa, Canada. Contact: Gerry Einarsson, Chair, (tel 613-824-2468, email einargk@rogers.com, url http://www.russona.com/issc21/).

MCNPX Advanced Workshop, Aug. 25-29, 2003, Los Alamos / Sante Fe. Contact: Bill Hamilton (tel 505-455-0312, email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com for details).

MCNP Course, Aug. 2003, (TBA), Los Alamos National Laboratory, Los Alamos, NM. Contact: Elizabeth Selcow (email selcow@lanl.gov, url http://www-xdiv.lanl.gov/x5/MCNP/ index.html).

September 2003

Workshop on Nuclear Data for the Transmutation of Nuclear Waste, Sept. 1-5, 2003, GSI-Darmstadt, Germany, Contact: Aleksandra Kelic (tel 49-0- 6159-71-2727, fax 49-0-6159-71-2785, email A.Kelic@gsi.de, url http://www-wnt.gsi.de/tramu).

Nuclear Energy for New Europe 2003, Sept. 8-11, 2003, Portorož, Slovenia, Contact: Tomaz Zagar (phone +386-1-588-5450, fax +386-1-561-2335, email PORT2003@ijs.si, url http://www.drustvo -js.si/port2003/).

Visual Editor for MCNP, Sept. 8-12, 2003, Richland, Washington. Contact: Randy Schwarz (email randyschwarz@mcnpvised.com, url http://www.mcnpvised.com/train.html)

9th International Conference on Environmental Remediation and Radioactive Waste Management, Sept. 21-25, 2003, Oxford, England. Contact: (url www.icemconf.com).

International Conference on Supercomputing in Nuclear Applications, SNA 2003, Sept. 22-24, 2003, Paris, France. Organizers: CEA, SFANS, co-organizer: OECD/NEA. (email SNA-2003@ cea.fr, url http://SNA-2003.cea.fr).

MCNPX Introductory Workshop, Sept/Oct (tbd), 2003, Europe. Contact: Bill Hamilton (tel 505-455-0312, Email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com for details).

October 2003

American Nuclear Society's Advances in Nuclear Fuel Management III Topical Meeting, Oct. 5-8, 2003, Hilton Head Island, SC. Contact: Youssef A. Shatilla (email shatilya@westinghouse.com, url http://rpd.ans.org/nfm.htm).

7th International Conference on Nuclear Criticality Safety (ICNC2003), Oct. 20-24, 2003, Contact: Dr. Yoshinori Miyoshi (tel +81-29-282-6671; fax +81-29-282-6798, email icnc03miyoshi@nucef.tokai. jaeri.go.jp, url http://www.icnc.jp/).

9th Triennial International Symposium in Radiation Physics, Oct. 27-31, 2003, Cape Town, South Africa. Contact: Dr. D. T. L. Jones (tel +27-21-843-1336, fax +27-21-843-3382, email Jones@tlabs.ac.za url www.medrad. tlabs.ac.za/isrp9.htm).

MCNPX Introductory Workshop, Sept/Oct (tbd), 2003, Europe. Contact: Bill Hamilton (tel 505-455-0312, Email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com for details).

November 2003

MCNPX Advanced Workshop, November, 2003, Japan. Contact: Bill Hamilton (tel 505-455-0312, email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com for details).

December 2003

The 11th International Conference on Fusion Reactor Materials (ICFRM-11), Dec. 7-12, 2003, Kyoto, Japan. Contact ICFRM-11 secretariat ( tel +81-774-38-3597, fax +81-774-38-3467, email icfrm@iae.kyoto-u.ac.jp, url http://icfrm.iae.kyoto-u.ac.jp).

May 2004

International Conference on Radiation Shielding (ICRS-10) and Topical Mtg. on Radiation Protection & Shielding (RPS 2004), May 9-14, 2004, Funchal, Madeira Island (Portugal). Contact: Conference Secretariat (email icrs-rps@itn.mces.pt, url http://www.itn.mces.pt/ICRS-RPS).
 
 

The nuclear systems literature (shielding, safety, materials) cited below has been reviewed and placed in the RSICC Information Storage and Retrieval Information System (SARIS), now searchable on the RSICC web server (http://www-rsicc.ornl.gov/SARIS.html). We now include medical physics in addition to material science, radiation dosimetry, radiation safety, reactor dynamics, reactor safeguards, risk assessment, waste management, fuel cycle, fusion and plasmas, high energy particle transport, and shielding. This early announcement is made as a service to the nuclear sciences community. Copies of the literature are not distributed by RSICC. They may generally be obtained from the author or from a documentation center such as the National Technical Information Service (NTIS), Department of Commerce, Springfield, Virginia 22161. For literature listed as available from INIS contact INIS Clearinghouse, International Atomic Energy Agency, P.O. Box 100, A-1400 Vienna.

J. Nucl. Mater., 307, 1-9. . . ITER Status, Design and Material Objectives.. . . Aymar, R. et al.. . . December 2002. . . ITER, Garching, Germany.

J. Nucl. Mater., 307, 21-30. . . Breeding Blanket Concepts for Fusion and Materials Requirements.. . . Raffray, A.R. et al.. . . December 2002. . . JAERI, Ibaraki-ken, Japan; Max Planck Inst. Plasma Physics, Garching, Germany; CEA Saclay, Gif-sur-Yvette, France; Forschungszentrum Karlsruhe, Germany.

J. Nucl. Mater., 307, 31-42. . . Scientific and Engineering Advances from Fusion Materials R&D.. . . Zinkle, S.J. et al.. . . December 2002. . . Oak Ridge National Laboratory, Oak Ridge, TN; EPFL, Villigen, Switzerland; Tohoku University, Miyagi, Japan.

J. Nucl. Mater., 307, 43-52. . . Plasma Facing and High Heat Flux Materials - Needs for ITER and Beyond.. . . Bolt, H. et al.. . . December 2002. . . Max Planck Inst. Plasma Physics, Garching, Germany; ITER, Garching, Germany; Forschungszentrum Julich, Germany; CSU Garching, Germany; JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 53-59. . . High Heat Flux Performance of Neutron Irradiated Plasma Facing Components.. . . Rodig, M. et al.. . . December 2002. . . Forschungszentrum Julich, Germany; JAERI, Ibaraki-ken, Japan; DVEfremov Inst. Electrophysics Apparatus, St. Petersburg, Russia; EFDA, Garching, Germany.

J. Nucl. Mater., 307, 60-68. . . Macroscopic Erosion of Divertor and First Wall Armour in Future Tokamaks.. . . Wuerz, H. et al.. . . December 2002. . . Forschungszentrum Karlsruhe, Germany; Luikov Inst. Heat & Mass Transfer, Minsk, Byelarus; Troitsk Inst. Innov. & Fusion Research, Troitsk, Russia.

J. Nucl. Mater., 307, 69-73. . . Melt Layer Erosion of Metallic Armour Targets During Off-Normal Events in Tokamaks.. . . Wuerz, H., Bazylev, B. . . . December 2002. . . Forschungszentrum Karlsruhe, Germany; Luikov Inst. Heat & Mass Transfer, Minsk, Byelarus.

J. Nucl. Mater., 307, 74-78. . . Prediction of Plastic Deformation of Fiber-Reinforced Copper Matrix Composites.. . . You, J.H., Bolt, H. . . . December 2002. . . Max Planck Inst. Plasma Physics, Garching, Germany.

J. Nucl. Mater., 307, 79-83. . . Deuterium Release and Microstructure of Tantalum-Tungsten Twin Limiter Exposed in TEXTOR-94.. . . Hirai, T. et al.. . . December 2002. . . KFA Julich, Germany; Nagoya Univ., Aichi, Japan; Doshisha Univ.,Kyoto, Japan; Forschungszentrum Julich, Germany; Fukuoka Univ., Japan; Univ. Tokushima, Japan; Russian, Acad. Sci., Moscow, Russia.

J. Nucl. Mater., 307, 84-88. . . Erosion and Re-Deposition Behavior of Plasma Facing Materials Due to Tokamak Plasma Disruption.. . . Liu, X. et al.. . . December 2002. . . Sw. Inst. Physics., Chengdu, China.

J. Nucl. Mater., 307, 89-94. . . Characterisation and Thermal Loading of Low-Z Coatings for the First Wall of W7-X.. . . Valenza, D. et al.. . . December 2002. . . Max Planck Inst. Plasma, Phys., Garching, Germany; Forschungszentrum Karlsruhe, Germany.

J. Nucl. Mater., 307, 95-99. . . Damage of Structural Materials for Fusion Devices Under Pulsed Ion and High Temperature Plasma Beams.. . . Pimenov, V.N. et al.. . . December 2002. . . Baikov Inst. Met. & Mat. Sci., Moscow, Russia; Inst. Plasma Phys. & Laswer Microfus, Warsaw, Poland; PN Lebedev Phys. Inst., Moscow, Russia; Pedag Univ. Tallinn, Estonia.

J. Nucl. Mater., 307, 100-105. . . Simulation Experimental Investigation of Plasma Off-Normal Events on Advanced Silicon Doped CFC-NS31.. . . Bonal, JP. et al.. . . December 2002. . . CTR ETUD Saclay, Gif-sur-Yvette, France.

J. Nucl. Mater., 307, 106-110. . . Melt Layer Behavior of Metal Targets Irradiated by Powerful Plasma Streams.. . . Bandura, A.N. et al.. . . December 2002. . . KIPT, Kharkov, Ukraine; Forschungszentrum Karlsruhe, Germany.

J. Nucl. Mater., 307, 111-115. . . Overview of Fuel Retention in Composite and Tungsten Limiters.. . . Rubel, M. et al.. . . December 2002. . . Royal Inst. Technol., Stockholm, Sweden; KFA Julich, Germany; Nagoya Univ., Aichi, Japan; Max Planck Inst. Plasma Phys., Garching, Germany.

J. Nucl. Mater., 307, 116-120. . . Development of Tungsten Coated First Wall and High Heat Flux Components for Application in ASDEX Upgrade.. . . Maier, H. et al.. . . December 2002. . . Max Planck Inst. Plasma Phys., Garching, Germany; KFA Julich, Germany.

J. Nucl. Mater., 307, 121-125. . . Properties of Plasma Sprayed Boron Carbide Protective Coatings for the First Wall in Fusion Experiments.. . . Doring, J.E. et al.. . . December 2002. . . KFA Julich, Germany.

J. Nucl. Mater., 307, 126-129. . . Modification of Tungsten Coated Carbon by Low Energy and High Flux Deuterium Irradiation.. . . Tokunaga, K. et al.. . . December 2002. . . Kyushu Univ., Fukuoka, Japan; Univ. California San Diego, La Jolla, CA; Natl. Inst. Fus. Sci., Gifu, Japan; Toyo Tanso Co. Ltd., Kagawa, Japan; Nippon Plansee, Tokyo, Japan.

J. Nucl. Mater., 307, 135-138. . . Effects of Helium Bombardment on the Deuterium Behavior in Tungsten.. . . Iwakiri, H. et al.. . . December 2002. . . Kyushu Univ., Fukuoka, Japan; Kyoto Univ., Japan.

J. Nucl. Mater., 307, 139-143. . . Erosion and Migration of Tungsten Employed at the Central Column Heat Shield of ASDEX Upgrade.. . . Krieger, K. et al.. . . December 2002. . . Max Planck Inst. Plasma Phys., Garching, Germany; Academy Sinica, Anhui, China.

J. Nucl. Mater., 307, 144-148. . . Non-Destructive Testing of CFC Monoblock Divertor Mock-Ups.. . . Ezato, K. et al.. . . December 2002. . . JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 149-153. . . Heat Load to a Tantalum-Tungsten Twin-Test-Limiter and the Effect to High-Z Core Plasma Concentration of TEXTOR-94.. . . Ohgo, T. et al.. . . December 2002. . . Fukuoka Univ., Japan; Doshisha Univ., Kyotanabe, Japan; Forschungszentrum, Julich, Germany; Kyoto Univ., Japan; Nagoya Univ., Aichi, Japan; Inst. High Temp., Moscow, Russia.

J. Nucl. Mater., 307, 154-158. . . Experimental and Computer Investigation of the Diagnostic Mirror Behavior Under Sputtering and Duct Material Deposition.. . . Bandourko, V.V. et al.. . . December 2002. . . Moscow Eng. Phys. Inst., Moscow, Russia.

J. Nucl. Mater., 307, 159-170. . . Experiment-Based Modeling of Hardening and Localized Plasticity in Metals Irradiated Under Cascade Damage Conditions.. . . Singh, B.N. et al.. . . December 2002. . . Riso Lab., Roskilde, Denmark; Univ. Calif. Los Angeles, CA; KFA Julich, Germany.

J. Nucl. Mater., 307, 171-178. . . Modeling the Multiscale Mechanics of Flow Localization-Ductility Loss in Irradiation Damaged BCC Alloys.. . . Odette, G.R. et al.. . . December 2002. . . Univ. Calif. Santa Barbara, CA; EPFL, Lausanne, Switzerland; Tohoku Univ., Miyagi, Japan.

J. Nucl. Mater., 307, 179-186. . . Development of an Extensive Database of Mechanical and Physical Properties for Reduced-Activation Martensitic Steel F82H.. . . Jitsukawa, S. et al.. . . December 2002. . . Def Acad., Kanagawa, Japan; NRG, Petten, Netherlands; Oak Ridge National Laboratory, Oak Ridge, TN; CEA Saclay, Gif-sur-Yvette, France; IMF, Karlsruhe, Germany; PSI, Villigen, Switzerland.

J. Nucl. Mater., 307, 187-191. . . Experimental Determination of the Effect of Helium on the Fracture Toughness of Steel.. . . Snead, L.L. et al.. . . December 2002. . . Oak Ridge National Laboratory, Oak Ridge, TN; Los Alamos National Lab., Los Alamos, NM.

J. Nucl. Mater., 307, 192-196. . . Effect of Periodic Temperature Variations on the Microstructure of Neutron-Irradiated Metals.. . . Zinkle, S.J. et al.. . . December 2002. . . Oak Ridge National Laboratory, Oak Ridge, TN; National Inst. Fus. Sci., Gifu, Japan; Riso National Lab., Roskilde, Denmark.

J. Nucl. Mater., 307, 197-202. . . Microstructure of Irradiated Ferritic/Martensitic Steels in Relation to Mechanical Properties.. . . Schaeublin, R. et al.. . . December 2002. . . EPFL, Villigen, Switzerland; PNL, Richland, WA.

J. Nucl. Mater., 307, 203-211. . . Microstructural Study of Irradiated Isotopically Tailored F82H Steel.. . . Wakai, E. et al.. . . December 2002. . . JAERI, Ibaraki-ken, Japan; Oak Ridge National Lab., Oak Ridge, TN; Tohoku Univ., Miyagi, Japan.

J. Nucl. Mater., 307, 212-216. . . Recent Results for the Ferritics Isotopic Tailoring (FIST) Experiment.. . . Gelles., D.S. et al.. . . December 2002. . . Hokkaido Univ., Hokkaido, Japan; JAERI, Ibaraki-ken, Japan; Muroran Inst. Technol., Hokkaido, Japan; Kyoto Univ., Japan; Oak Ridge National Laboratory, Oak Ridge, TN.

J. Nucl. Mater., 307, 217-221. . . Creep Behavior of Reduced Activation Martensitic Steel F82H Injected with a Large Amount of Helium.. . . Yamamoto, N. et al.. . . December 2002. . . Natl. Inst. Mat. Sci., Ibaraki-ken, Japan; JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 222-228. . . Pros and Cons of Nickel- and Boron-Doping to Study Helium Effects in Ferritic/Martensitic Steels.. . . Hashimoto, N. et al.. . . December 2002. . . Oak Ridge National Lab., Oak Ridge, TN; JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 229-235. . . Evolution of the Mechanical Properties and Microstructure of Ferritic-Martensitic Steels Irradiated in the BOR-60 Reactor.. . . Shamardin, V.K. et al.. . . December 2002. . . Resh Inst. Atom. Reactors, Ulyanovsk Region, Russia.

J. Nucl. Mater., 307, 236-239. . . Assessment of Mechanical Properties of the Martensitic Steel EUROFER97 by Means of Punch Tests.. . . Ruan, Y. et al.. . . December 2002. . . Ecole Polytech. Fed. Lausanne, Villigen, Switzerland.

J. Nucl. Mater., 307, 240-244. . . Development of a Non-Destructive Testing Technique Using Ultrasonic Wave for Evaluation of Irradiation Embrittlement in Nuclear Materials.. . . Ishii, T. et al.. . . December 2002. . . JAERI, Ibaraki-ken, Japan; Tokyo Inst. Technol., Tokyo, Japan.

J. Nucl. Mater., 307, 245-249. . . Tensile Properties and Transition Behaviour of RAFM Steel Plate and Welds Irradiated Up to 10 DPA at 300 Degrees C.. . . Rensman, J. et al.. . . December 2002. . . Nucl. Res. & Consultancy Group, Petten, Netherlands.

J. Nucl. Mater., 307, 250-255. . . Characteristics of Unirradiated and 60 Degrees C, 2.7 DPA Irradiated Eurofer97.. . . Rensman, J. et al.. . . December 2002. . . Nucl. Res. & Consultancy Group, Petten, Netherlands; ECN, Petten, Netherlands.

J. Nucl. Mater., 307, 256-259. . . Tensile Response of Low Activation Ferritic Steels Irradiated in ORR at Temperatures in the Range 60-400 Degrees C.. . . Gelles, D.S., Hamilton, M.L. . . . December 2002. . . Pacific NW National Laboratory, Richland, WA.

J. Nucl. Mater., 307, 260-265. . . Evaluation of Hardening Behaviour of Ion Irradiated Reduced Activation Ferritic/Martensitic Steels by Ail Ultra-Micro-Indentation Technique.. . . Ando, M. et al.. . . December 2002. . . JAERI, Ibaraki-ken, Japan; Kyoto Univ., Japan.

J. Nucl. Mater., 307, 266-271. . . Structural Evaluation in Modified 9Cr-1Mo Ferritic/Martensitic Steel Irradiated with Mixed High-Energy Proton and Neutron Spectra at Low Temperatures.. . . Sencer, B.H. et al.. . . December 2002. . . Univ. Michigan, Ann Arbor, MI; Pacific NW National Lab., Richland, WA; New Mexico Inst. Min. & Technol., Socorro, NM; Los Alamos National Laboratory, Los Alamos, NM.

J. Nucl. Mater., 307, 272-277. . . Formation Process of Dislocation Loops in Iron Under Irradiations with Low-Energy Helium, Hydrogen Ions or High-Energy Electrons.. . . Arakawa, K. et al.. . . December 2002. . . Shimane Univ., Shimane, Japan; Osaka Univ., Osaka, Japan.

J. Nucl. Mater., 307, 278-282. . . Effect of Triple Ion Beams in Ferritic/Martensitic Steel on Swelling Behavior.. . . Wakai, E. et al.. . . December 2002. . . JAERI, Ibaraki-ken, Japan; Hokkaido Univ., Japan.

J. Nucl. Mater., 307, 283-288. . . Phase Stability of Oxide Dispersion Strengthened Ferritic Steels in Neutron Irradiation.. . . Yamashita, S. et al.. . . December 2002. . . Hokkaido Univ., Japan; Japan Nucl. Cycle Dev. Inst., Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 289-292. . . Microstructure and Hardness of HIP-Bonded Regions in F82H Blanket Structures.. . . Furuya, K. et al.. . . December 2002. . . JAERI, Ibaraki-ken, Japan; Iwate Univ., Iwate, Japan.

J. Nucl. Mater., 307, 293-298. . . Microstructural Analysis of Mechanically Tested Reduced-Activation Ferritic/Martensitic Steels.. . . Tanigawa, H. et al.. . . December 2002. . . JAERI, Ibaraki-ken, Japan; Kyoto Univ., Kyoto, Japan.

J. Nucl. Mater., 307, 299-303. . . Void Swelling in Reduced Activation Ferritic/Martensitic Steels Under Ion-Beam Irradiation to High Fluences.. . . Ogiwara, H. et al.. . . December 2002. . . Kyoto Univ., Kyoto, Japan; JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 304-307. . . Radiation Effects on Low Cycle Fatigue Properties of Reduced Activation Ferritic/Martensitic Steels.. . . Hirose, T. et al.. . . December 2002. . . Kyoto Univ., Kyoto, Japan; JAERI, Ibaraki-ken, Japan; Tohoku Univ., Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 308-311. . . Evaluation of Radiation Hardening in Fe Alloys Under Heavy Ion Irradiation by Micro-Indentation Technique.. . . Sekimura, N. et al.. . . December 2002. . . Univ. Tokyo, Tokyo, Japan.

J. Nucl. Mater., 307, 312-316. . . Swelling Behavior of TIG-Welded F82HIEA Heat.. . . Sawai, T. et al.. . . December 2002. . . JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 317-321. . . Dissolution Kinetics of Intermetallics in Aging Austenitic Steels During Neutron Irradiation.. . . Sagaradze, V.V. et al.. . . December 2002. . . Inst. Met. Phys., Ekaterinburg, Russia.

J. Nucl. Mater., 307, 322-326. . . The Primary Origin of Dose Rate Effects on Microstructural Evolution of Austenitic Alloys During Neutron Irradiation.. . . Okita, T. et al.. . . December 2002. . . Univ. Tokyo, Japan; Pacific NW Natl. Lab., Richland, WA.

J. Nucl. Mater., 307, 327-330. . . Effect of Weld Thermal Cycle, Stress and Helium Content on Helium Bubble Formation in Stainless Steels.. . . Kawano, S. et al.. . . December 2002. . . Toshiba Co. Ltd., Kanagawa, Japan; Kyushu Univ., Fukuoka, Japan; Tohoku Univ., Miyagi, Japan.

J. Nucl. Mater., 307, 331-334. . . Evaluation of In-Pile and Out-of-Pile Stress Relaxation in 316L Stainless Steel Under Uniaxial Loading.. . . Kaji, Y. et al.. . . December 2002. . . JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 335-338. . . Microstructure of Neutron Irradiated SS316L/DS-Cu Joint.. . . Watanabe, H. et al.. . . December 2002. . . Kyushu Univ., Fukuoka, Japan; Pacific NW Natl. Lab., Richland, WA; Hitachi Ltd., Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 339-342. . . Void Swelling at Low Displacement Rates in Annealed 12X18H9T Stainless Steel at 4-56 DPA and 280-332 Degrees C.. . . Porollo, S.I. et al.. . . December 2002. . . Inst. Phys. & Power Eng., Kaluga Region, Russia; PNNL, Richland, WA.

J. Nucl. Mater., 307, 343-346. . . Effect of Chemical Composition on Irradiation Creep of Stainless Steels Irradiated in the BOR-60 Reactor at 420 Degrees C.. . . Shamardin, V.K, Neustroev, V.S... . . December 2002. . . RIAR, Ulyanovsk Region, Russia.

J. Nucl. Mater., 307, 347-351. . . Irradiation-Assisted SCC Susceptibility of HIPed 316LN-IG Stainless Steel Irradiated at 473 K to 1 DPA.. . . Miwa, Y. et al.. . . December 2002. . . JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 352-356. . . Swelling of Cold-Worked Austenitic Stainless Steels Irradiated in HFIR Under Spectrally Tailored Conditions.. . . Wakai, E. et al.. . . December 2002. . . JAERI, Ibaraki-ken, Japan; Oak Ridge National Laboratory, Oak Ridge, TN.

J. Nucl. Mater., 307, 357-361. . . The Performance of Chinese 316L and 316Ti Stainless Steel Irradiated at 300, 400, 500, and 600 Degrees C in HFIR JP-23 Test Capsule.. . . Yu. J. et al.. . . December 2002. . . China Inst. Atom. Energy, Beijing, China; PNNL, Richland, WA.

J. Nucl. Mater., 307, 362-366. . . Microstructure Development and Helium Behavior in Nickel and Vanadium Base Alloys.. . . Kalashnikov, A.N. et al.. . . December 2002. . . Lomonosov State Univ., Moscow, Russia.

J. Nucl. Mater., 307, 367-373. . . Effect of Solute Atoms on Swelling in Ni Alloys and Pure Ni Under He+ Ion Irradiation.. . . Wakai, E. et al.. . . December 2002. . . JAERI, Ibaraki-ken, Japan; Univ. E. Asia, Yamaguchi, Japan; Sumitomo Met. Co. Ltd., Hyogo, Japan; Nagoya Univ., Aichi, Japan; Univ. Osaka Prefecture, Osaka, Japan.

J. Nucl. Mater., 307, 374-379. . . The Microstructure and Tensile Properties of Pure Ni Single Crystal Irradiated with High Energy Protons.. . . Yao, Z. et al.. . . December 2002. . . Fusion Technology Mat., Villigen, Switzerland.

J. Nucl. Mater., 307, 380-384. . . Influence of Temperature Change on Microstructure Evolution in Ni Alloys Irradiated with Neutrons.. . . Xu, Q., Yoshiie, T. . . . December 2002. . . Kyoto Univ., Osaka, Japan.

J. Nucl. Mater., 307, 385-388. . . Effects of Solid Transmutation and Helium on Microstructural Evolution in Neutron-Irradiated Vanadium.. . . Sato, T. et al.. . . December 2002. . . Univ. Tokyo, Japan.

J. Nucl. Mater., 307, 389-392. . . Phase Stability and Mechanical Properties of Irradiated Ti-Al-V Intermetallic Compound.. . . Sawai, T. et al.. . . December 2002. . . JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 393-397. . . Microstructural Examination of Irradiated and Unirradiated V-4Cr-4Ti Pressurized Creep Tubes.. . . Gelles, D.S.. . . December 2002. . . Pacific NW Natl. Lab., Richland, WA.

J. Nucl. Mater., 307, 398-402. . . Effects of Temperature Change on Microstructural Evolution in Vanadium Alloys Under Ion Irradiation Up to High Damage Levels.. . . Nita, N. et al.. . . December 2002. . . Tohoku Univ., Miyagi, Japan; Univ. Tokyo, Ibaraki-ken, Japan; Hiroshima Inst. Technol., Hiroshima, Japan.

J. Nucl. Mater., 307, 403-407. . . Effects of Temperature Change on Vanadium Alloys Irradiated in HFIR.. . . Watanabe, H. et al.. . . December 2002. . . Kyushu Univ., Fukuoka, Japan; Natl. Inst. Fus. Sci, Gifu, Japan.

J. Nucl. Mater., 307, 408-411. . . Oxide Formation of a Purified V-4Cr-4Ti Alloy During Heat Treatment and Ion Irradiation.. . . Watanabe, H. et al.. . . December 2002. . . Kyushu University, Fukuoka, Japan; Natl. Inst. Fus. Sci., Gifu, Japan.

J. Nucl. Mater., 307, 412-415. . . Microstructure in Vanadium Irradiated by Simultaneous Multi-Ion Beam of Hydrogen, Helium and Nickel Ion.. . . Mukouda, I. et al.. . . December 2002. . . Hiroshima Univ., Hiroshima, Japan; JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 416-420. . . Tensile and Fracture Toughness Properties of Unirradiated and Neutron Irradiated Titanium Alloys.. . . Tahtinen, S. et al.. . . December 2002. . . VTT Ind Syst., Espoo, Finland; Riso Natl. Lab., Roskilde, Denmark; PNNL, Richland, WA.

J. Nucl. Mater., 307, 421-425. . . Irradiation Behaviour of Titanium Alloys for ITER Blanket Modules Flexible Attachment.. . . Rodchenkov, B.S. et al.. . . December 2002. . . ENEA, Moscow, Russia; Max Planck Inst. Plasma Phys., Garching, Germany; ITER Garching Joint Work Site, Garching, Germany.

J. Nucl. Mater., 307, 426-430. . . Change of Thermal Diffusivity and Lattice Constants of W-5% Re-HfC Alloys Irradiated in a Fission Reactor.. . . Fujitsuka, M. et al.. . . December 2002. . . Natl. Inst. Mat. Sci., Ibaraki-ken, Japan; Thailand Inst. Sci. &Technol. Res., Bangkok, Thailand; Tohoku Univ., Ibaraki-ken, Japan; Kitami Inst. Technol., Hokkaido, Japan.

J. Nucl. Mater., 307, 431-438. . . Effect of the Bake-Out Regime of Copper-Based Alloys on the Recovery of Properties and Copper/Steel Joints.. . . Fabritsiev, S.A.,Pokrovsky, A. S. . . . December 2002. . . Sci. Res. Inst. Atom. Reactors, Dimitrovgrad, Russia.

J. Nucl. Mater., 307, 439-443. . . Post-Irradiation Annealing of Neutron Irradiated CuCrZr.. . . Edwards, D.J. et al.. . . December 2002. . . PNNL, Richland, WA; Riso Natl. Lab., Roskilde, Denmark; Kyoto Univ., Osaka, Japan.

J. Nucl. Mater., 307, 444-449. . . Low Void Swelling in Dispersion Strengthened Copper Alloys Under Single-Ion Irradiation.. . . Hatakeyama, M. et al.. . . December 2002. . . Kyushu Univ., Fukuoka, Japan; JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 450-454. . . Microstructure Evolution in D-T Neutron Irradiated Silver.. . . Sugio, K. et al.. . . December 2002. . . Hiroshima Univ., Japan; Hiroshima Inst. Technol., Japan; JAERI,Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 455-465. . . Ferritic/Martensitic Steels - Overview of Recent Results.. . . Klueh, R.L. et al.. . . December 2002. . . Oak Ridge National Laboratory, Oak Ridge, TN; JAERI, Ibaraki-kenJapan; IAE Kyoto Univ., Japan; Univ. Calif. Santa Barbara, CA; NRG, Petten, Netherlands; FTM, Villigen, Switzerland.

J. Nucl. Mater., 307, 466-470. . . Investigation of Heat Treatment Conditions on the Structure of 12% Chromium Reduced Activation.. . . Leonteva-Smirnova, M.V. et al.. . . December 2002. . . Bochvar. Res. Inst. Inorgan Mat., Moscow, Russia.

J. Nucl. Mater., 307, 471-474. . . Thermal Fatigue Crack Propagation Behaviour of F82H Ferritic Steel.. . . Kudo, Y. et al.. . . December 2002. . . JAERI, Ibatraki-ken, Japan; Mitsubishi Heavy Ind. Co., Hyogo, Japan; Univ. Tsukuba, Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 475-478. . . Effect of the Thermal Cycling on Impurity Grain Boundary Segration in Maraging Steel.. . . Ilyin, A.M. et al.. . . December 2002. . . Kazakhstan State Univ., Alma Ata, Kazakhstan.

J. Nucl. Mater., 307, 479-483. . . Behavior of Eurofer97 Reduced Activation Martensitic Steel Upon Heating and Continuous Cooling.. . . Alamo, A., Danon, A. . . . December 2002. . . CEA, Gif-sur-Yvette, France.

J. Nucl. Mater., 307, 484-489. . . Tensile and Fracture Toughness Properties of MA957: Implications to the Development of Nanocomposited Ferritic Alloys.. . . Alinger, M.J. et al.. . . December 2002. . . Univ. California, Santa Barbara, CA.

J. Nucl. Mater., 307, 490-494. . . Effects of Precipitation Morphology on Toughness of Reduced Activation Ferritic/Martensitic Steels.. . . Sadasegawa, H. et al.. . . December 2002. . . Kyoto Univ., Japan; Univ. Tokyo, Japan; Nippon Steel Corp., Chiba, Japan.

J. Nucl. Mater., 307, 495-499. . . Metallurgical Properties of Reduced Activation Martensitic Steel Eurofer'97 in the As-Received Condition and After Thermal Ageing.. . . Fernandez, P. et al.. . . December 2002. . . CIEMAT, Madrid, Spain.

J. Nucl. Mater., 307, 500-504. . . Thermo-Mechanical Fatigue Behavior of Reduced Activation Ferrite/Martensite Stainless Steels.. . . Rodrian, D., Petersen, C. . . . December 2002. . . Forschungszentrum Karlsruhe, Germany.

J. Nucl. Mater., 307, 505-508. . . In Situ Phase Characterization in Tempering and Aging of Fe-Cr-W Steels.. . . Inoue, N. et al.. . . December 2002. . . Natl. Inst. Fus. Sci., Gifu, Japan; Tokai Univ., Kanagawa, Japan.

J. Nucl. Mater., 307, 509-513. . . Mechanical and Microstructural Behaviour of Isothermally and Thermally Fatigued Ferritic/Martensitic Steels.. . . Armas, A.F. et al.. . . December 2002. . . Forschungszentrum Karlsruhe, Germany; Univ. Nacl. Rosario, SantaFe, Argentina.

J. Nucl. Mater., 307, 514-520. . . Modelling of the Effect of Precipitates on Work-Hardening, Ductility and Impact Behaviour of Ferritic-Martensitic Cr Steels.. . . Preininger, D.. . . December 2002. . . Forschungszentrum Karlsruhe, Germany.

J. Nucl. Mater., 307, 521-526. . . High Resistance to Helium Embrittlement in Reduced Activation Martensitic Steels.. . . Kimura, A. et al.. . . December 2002. . . Kyoto Univ., Japan; Tohoku Univ., Miyagai, Japan; Kyushu Univ.,Fukuoka, Japan; Lawrence Livermore Natl. Lab., Livermore, CA.

J. Nucl. Mater., 307, 527-531. . . Comparison of In-Beam Fatigue Behavior Between Austenitic and Ferritic Steels at 60 Degrees C.. . . Murase, Y. et al.. . . December 2002. . . Kyushu Univ., Fukuoka, Japan.

J. Nucl. Mater., 307, 532-535. . . Heat Resistant Reduced Activation 12% Cr Steel of 16Cr12W2VTaB Type-Advanced Structural Material for Fusion and Fast Breeder Power Reactors.. . . Iotukhovskiy, A.G. et al.. . . December 2002. . . Bochvar. Inst., Moscow, Russia.

J. Nucl. Mater., 307, 536-539. . . On the Mechanical Properties of the Advanced Martensitic Steel EUROFER 97.. . . Spatig, P. et al.. . . December 2002. . . Ecole Polytech Fed. Lausanne, Villigen, Switzerland; Univ. Calif. Santa Barbara, CA.

J. Nucl. Mater., 307, 540-543. . . The Effect of Hot Isostatic Pressing Parameters on Microstructure and Mechanical Properties of Eurofer Powder HIPed Material.. . . Gentzbittel, J.M. et al.. . . December 2002. . . CEA Grenoble, France.

J. Nucl. Mater., 307, 544-546. . . Solubility of Uranium at Very Low Concentration in RAFM Steel.. . . Paul, A. et al.. . . December 2002. . . Univ. Sevilla, Seville, Spain; Inst. Technol. & Nucl. Sacavem, Portugal; Univ. Lisbon, Portugal.

J. Nucl. Mater., 307, 547-554. . . Vanadium Alloys - Overview and Recent Results.. . . Muroga, T. et al.. . . December 2002. . . Tohoku Univ., Miyagi, Japan; Bochvar. Res. Inst., Moscow, Russia; Tohoku Univ., Miyagai, Japan; Argonne Natl. Lab, Argonne, IL; SW Inst. Phys., Chengdu, China; Oak Ridge Natl. Lab., Oak Ridge, TN.

J. Nucl. Mater., 307, 555-559. . . Fabrication Using a Levitation Melting Method of V-4Cr-4Ti-Si-A1-Y Alloys and Their Mechanical Properties.. . . Chuto, T. et al.. . . December 2002. . . Tohoku Univ., Miyagi, Japan; Natl. Inst. Fus. Sci., Toki, Japan.

J. Nucl. Mater., 307, 560-565. . . Oxygen Embrittlement of Vanadium Alloys With and Without Surface Oxide Formation.. . . Pint, B.A., DiStefano, J.R.. . . December 2002. . . Oak Ridge Natl. Lab., Oak Ridge, TN.

J. Nucl. Mater., 307, 560-565. . . Oxygen Embrittlement of Vanadium Alloys With and Without Surface Oxide Formation.. . . . . . December 2002. . . Oak Ridge Natl. Lab., Oak Ridge, TN.

J. Nucl. Mater., 307, 566-570. . . The Influence of Hydrogen on Tensile Properties of V-Base Alloys Developed in China.. . . Chen, J.M. et al.. . . December 2002. . . SW Inst. Phys., Chengdu, China.

J. Nucl. Mater., 307, 571-575. . . Fracture Properties of High-Purity V-4Cr-4Ti Alloy (NIFS-HEAT-2) at Room Temperature.. . . Nishimura, A. et al.. . . December 2002. . . Natl. Inst. Fus. Sci., Gifu, Japan.

J. Nucl. Mater., 307, 576-579. . . Hydrogen Solubility in V-4Cr-4Ti Alloy.. . . Buxbaum, R.E. et al.. . . December 2002. . . Argonne Natl. Lab., Argonne, IL; REB Resh., Ferndale, MI.

J. Nucl. Mater., 307, 580-584. . . Surface Segregation and Oxidation of Ti in a V-Ti Alloy.. . . Hayakawa, R. et al.. . . December 2002. . . Toyama Univ., Toyama, Japan; Inst. Nucl. Safety Syst., Fukui, Japan; Tohoku Univ., Miyagi, Japan.

J. Nucl. Mater., 307, 585-590. . . Uniaxial Creep Behavior of V-4Cr-4Ti Alloy.. . . Natesan, K. et al.. . . December 2002. . . Argonne National Laboratory, Argonne, IL.

J. Nucl. Mater., 307, 591-595. . . Influence of Alloying and Impurity Element Contents on V-Ti-Cr Alloy Properties.. . . Evtikhin, V.A. et al.. . . December 2002. . . State Enterprise Red Star, Moscow, Russia; Bochvar. Res. Inst. Moscow, Russia; RAS, Moscow, Russia.

J. Nucl. Mater., 307, 596-600. . . Investigating Solute Interactions in V-4Cr-4Ti Based on Tensile Deformation Behavior of Vanadium.. . . Hoelzer, D.T., Rowcliffe, A.F. . . . December 2002. . . Oak Ridge National Laboratory, Oak Ridge, TN.

J. Nucl. Mater., 307, 601-604. . . Effects of Doping Elements on Oxidation Properties of V-Cr-Ti Type Alloys in Several Environments.. . . Fujiwara, M. et al.. . . December 2002. . . Tohoku Univ., Miyagi, Japan; Argonne National Lab., Argonne, IL.

J. Nucl. Mater., 307, 605-609. . . Performance of V-4Cr-4Ti Material Exposed to the DIII-D Tokamak Environment.. . . Tsai, H. et al.. . . December 2002. . . Argonne National Lab., Argonne, IL; Gen. Atomic Co., San Diego,CA; Oak Ridge National Laboratory, Oak Ridge, TN.

J. Nucl. Mater., 307, 610-614. . . High Temperature Performance of Highly Purified V-4Cr-4Ti Alloy, NIFS-Heat1.. . . Fukumoto, K. et al.. . . December 2002. . . Tohoku Univ., Miyagi, Japan.

J. Nucl. Mater., 307, 615-619. . . Creep of V-4Cr-4Ti in a Lithium Environment.. . . Grossbeck, M.L.. . . December 2002. . . Oak Ridge National Laboratory, Oak Ridge, TN.

J. Nucl. Mater., 307, 620-624. . . Effect of Impurity Levels on Precipitation Behavior in the Low-Activation V-4Cr-4Ti Alloys.. . . Heo, N.J. et al.. . . December 2002. . . Grad. Univ. Adv. Studies., Gifu, Japan; Natl. Inst. Fus. Sci., Gifu, Japan; Tohoku Univ., Miyagi, Japan.

J. Nucl. Mater., 307, 625-629. . . Hydride Formation and Fracture of Vanadium Alloys.. . . Torres, P. et al.. . . December 2002. . . Hokkaido Univ., Japan.

J. Nucl. Mater., 307, 630-637. . . Beryllium for Fusion Application - Recent Results.. . . Khomutov., A. et al.. . . December 2002. . . Bochvar. Inst. Moscow, Russia; EURATOM, Garching, Germany; JAERI, Ibaraki-ken, Japan; Nucl. Fus. Inst., Moscow, Russia; Idaho Natl. Engn. & Environm. Lab., Idaho Falls, ID.

J. Nucl. Mater., 307, 638-642. . . Compatibility Between Be12Ti and SS316LN.. . . Kawamura, H. et al.. . . December 2002. . . JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 643-646. . . Elemental Characterisation of Beryllium and Electrical Behaviour of Their Pebbles Beds.. . . Alves, E. et al.. . . December 2002. . . Inst. Technol. & Nucl., Sacavem, Portugal; Univ. Lisbon, Portugal, Culham Sci. Ctr., Oxon, England.

J. Nucl. Mater., 307, 647-652. . . Effects of Neutron Irradiation at 70-200 Degrees C in Beryllium.. . . Chakin, V.P. et al.. . . December 2002. . . Res. Inst. Atom. Reactors, Ulyanovsk Region, Russia; All Russian Res. Inst., Moscow, Russia.

J. Nucl. Mater., 307, 653-656. . . Tritium Release Properties of Neutron-Irradiated Be12Ti.. . . Uchida, M. et al.. . . December 2002. . . JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 657-663. . . Evolution of Beryllium Microstructure Under High-Dose Neutron Irradiation.. . . Ostrovsky, Z.Y., Chakin, V.P.. . . December 2002. . . Resh. Inst. Atom. Reactors, Ulyanovsk Region, Russia.

J. Nucl. Mater., 307, 664-667. . . Influence of High Dose Neutron Irradiation on Thermal Conductivity of Beryllium.. . . Syslov, D.N. et al.. . . December 2002. . . Resh. Inst. Atom. Reactors, Ulyanovsk Region, Russia.

J. Nucl. Mater., 307, 668-672. . . Specification of Properties and Design Allowables for Copper Alloys Used in HHF Components of ITER.. . . Kalinin, G.M. et al.. . . December 2002. . . ITER, Garching, Germany; Ifremov Inst., St. Petersburg, Russia;Riso Natl. Lab., Roskilde, Denmark; VTT Mfg. Technol., Espoo, Finland; Oak Ridge National Lab., Oak Ridge, TN.

J. Nucl. Mater., 307, 673-676. . . Effect of Heat Treatments on the Properties of CuCrZr Alloys.. . . Ivanov, A.D. et al.. . . December 2002. . . Eng. Ctr. Nucl. Equipment, Moscow, Russia; Tsvetmetobrabotka Inst., Moscow, Russia; Max Planck Inst. Plasma Phys., Garching, Germany.

J. Nucl. Mater., 307, 677-680. . . Influence of the Manufacturing Heat Cycles on the CuCrZr Properties.. . . Merola, M. et al.. . . December 2002. . . EFDA Close Support Unit, Garching, Germany; ENEA, Frascati, Italy, and Bologna, Italy; Politecn Turin, Turin, Italy.

J. Nucl. Mater., 307, 681-685. . . Strength of Copper Alloys in High Temperature Environment.. . . Nomura, Y. et al.. . . December 2002. . . Univ. Tsukuba, Ibaraki-ken, Japan; Mitsubishi Heavy Ind. Co. Ltd., Hyogo, Japan.

J. Nucl. Mater., 307, 686-690. . . Material Properties and Consequences on the Quality of Torre Supra Plasma Facing Components.. . . Schlosser, J. et al.. . . December 2002. . . CEA Cadarache, St. Paul-Les-Durance, France; Plansee AG, Reutte, Austria.

J. Nucl. Mater., 307, 691-695. . . Discontinuously Reinforced Titanium Matrix Composites for Fusion Applications.. . . de Castro, V. et al.. . . December 2002. . . Univ. Carlos III Madrid, Leganes, Spain; EPFL, Villigen, Switzerland.

J. Nucl. Mater., 307, 696-700. . . Structure-Mechanics Relationships in Proton Irradiated Pure Titanium.. . . Leguey, T. et al.. . . December 2002. . . EPFL, Villigen, Switzerland; Univ. Carlos III Madrid, Leganes, Spain.

J. Nucl. Mater., 307, 701-704. . . The Effect of Pre-Deformation on the Ductility of Chromium.. . . Wadsack, R. et al.. . . December 2002. . . Austrian Acad. Sci., Leoben, Austria; Plansee Ag., Reutte, Austria.

J. Nucl. Mater., 307, 705-709. . . Effects of Strain Rate on Tensile Properties of TZM and Mo-5%Re.. . . Filacchioni, G. et al.. . . December 2002. . . ENEA, Rome, Italy.

J. Nucl. Mater., 307, 710-714. . . Effect of Substrate Temperature on Microstructure and Deuterium Retention of Molybdenum Co-Deposition with Oxygen.. . . Miyamoto, M. et al.. . . December 2002. . . Kyushu Univ., Fukuoka, Japan; Forschungszentrum Julich, Germany.

J. Nucl. Mater., 307, 715-718. . . Isotope Separation of Silicon and Molybdenum Using a Free Electron Laser.. . . Noda, T. et al.. . . December 2002. . . Natl. Inst. Mat. Sci., Ibaraki-ken, Japan; Los Alamos National Lab., Los Alamos, NM.

J. Nucl. Mater., 307, 719-722. . . Disruption Tests on Repaired Tungsten by CVD Coating.. . . Taniguchi, M. et al.. . . December 2002. . . JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 723-728. . . Flux Dependence of Deuterium Retention in Single Crystal Tungsten.. . . Poon, M. et al.. . . December 2002. . . Univ. Toronto, Canada.

J. Nucl. Mater., 307, 729-734. . . Studies on Retention of Tritium Implanted into Tungsten by Beta-Ray-Induced X-Ray Spectrometry.. . . Matsuyama, M. et al.. . . December 2002. . . Toyama Univ., Toyama, Japan; Kyushu University, Fukuoka, Japan.

J. Nucl. Mater., 307, 739-742. . . Vaporization Properties of the Sn-25 at.%Li Alloy.. . . Anderl, R.A. et al.. . . December 2002. . . Idaho NEEL, Idaho Falls, ID.

J. Nucl. Mater., 307, 743-748. . . Fabrication and Properties of a Tin-Lithium Alloy.. . . Natesan, K., Ruther, W.E.. . . December 2002. . . Argonne National Lab., Argonne, IL.

J. Nucl. Mater., 307, 749-757. . . Perspective of ODS Alloys Application in Nuclear Environments.. . . Fujiwara, M., Ukai, S. . . December 2002. . . Japan Nucl. Cycle Dev. Inst., Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 758-762. . . Consolidation Process Study of 9Cr-ODS Martensitic Steels.. . . Ukai, S. et al.. . . December 2002. . . Japan Nucl. Cycle Dev. Inst., Ibaraki-ken, Japan; Kobelco Res. Inst., Hyogo, Japan; Kobe Special Tube Co., Hyogo, Japan.

J. Nucl. Mater., 307, 763-768. . . Long-Term High Temperature Oxidation Behavior of ODS Ferritics.. . . Wright, I.G., Pint, B.A. . . . December 2002. . . Oak Ridge National Lab., Oak Ridge, TN.

J. Nucl. Mater., 307, 769-772. . . Mechanical and Microstructural Properties of a Hipped RAFM ODS-Steel.. . . Lindau, R. et al.. . . December 2002. . . Forschungszentrum Karlsruhe, Germany.

J. Nucl. Mater., 307, 773-777. . . Tensile and Creep Properties of an Oxide Dispersion-Strengthened Ferritic Steel.. . . Klueh, R.L. et al.. . . December 2002. . . Oak Ridge National Lab., Oak Ridge, TN; Nagoya Univ., Aichi, Japan.

J. Nucl. Mater., 307, 778-782. . . Microstructure and Mechanical Properties of Two ODS Ferritic/Martensitic Steels.. . . Schaeublin, R. et al.. . . December 2002. . . EPFL, Villigen, Switzerland.

J. Nucl. Mater., 307, 783-787. . . Structure, Radiation Resistance and Thermal Creep of ODS Ferritic Steels.. . . Goshchitskii, B.M. et al.. . . December 2002. . . RAS, Ekaterinburg, Russia; Gen. Res. Inst. Non Ferrous. Met., Beijing, China; Cent. Iron & Steel Res. Inst., Beijing, China.

J. Nucl. Mater., 307, 788-792. . . Burst Properties of Irradiated Oxide Dispersion Strengthened Ferritic Steel Claddings.. . . Yoshitake, T. et al.. . . December 2002. . . Japan Nucl. Cycle Dev. Inst., Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 793-797. . . Displacement Damage Parameters for Fusion Breeder Blanket Materials Based on BCA Computer Simulations.. . . Leichtle, D.. . . December 2002. . . Forschungszentrum Karlsruhe, Germany.

J. Nucl. Mater., 307, 798-802. . . Activation Characteristics of a Solid Breeder Blanket for a Fusion Power Demonstration Reactor.. . . Fischer, U.,Tsige-Tamirat, H. . . . December 2002. . . Forschungszentrum Karlsruhe, Germany.

J. Nucl. Mater., 307, 803-806. . . Fabrication of Li2TiO3 Pebbles by the Extrusion-Spheronisation-Sintering Process.. . . Roux, N., Lulewicz, J.D. . . . December 2002. . . Center Etud. Saclay, Gif-sur-Yvette, France.

J. Nucl. Mater., 307, 807-810. . . Thermal Creep of Granular Breeder Materials in Fusion Blankets.. . . Buhler, L., Reimann, J.. . . December 2002. . . Forschungszentrum Karlsruhe, Germany.

J. Nucl. Mater., 307, 811-816. . . Characterisation of Ceramic Breeder Materials for the Helium Cooled Pebble Bed Blanket.. . . Piazza, G. et al.. . . December 2002. . . Forschungszentrum Karlsruhe, Germany; CEA, Gif-sur-Yvette, France.

J. Nucl. Mater., 307, 817-822. . . In-Pile Test of Li2TiO3 Pebble Bed with Neutron Pulse Operation.. . . Tsuchiya, K. et al.. . . December 2002. . . JAERI, Ibaraki-Ken, Japan; ITER, Garching, Germany; Sangyo Kagaku, Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 823-826. . . Influence of Neutron Irradiation on the Strength Characteristics of Lithium Ceramic Pellets for Fusion Reactor Blankets.. . . Kapychev, V. et al.. . . December 2002. . . JAERI, Ibaraki-Ken, Japan; ITER, Garching, Germany; Sangyo Kagaku, Ibaraki-ken, Japan.

J. Nucl. Mater., 307, 827-831. . . Numerical Simulation of Ceramic Breeder Pebble Bed Thermal Creep Behavior.. . . Ying. A. et al.. . . December 2002. . . Univ. Calif. Los Angeles, CA.

J. Nucl. Mater., 307, 832-836. . . In-Pile Performance of a Double-Walled Tube and a Tritium Permeation Barrier.. . . Magielsen, A.J. et al.. . . December 2002. . . CEA, Grenoble, France; JRCIE, Petten, Netherlands.

J. Nucl. Mater., 307, 837-841. . . Li2TiO3 Pebbles Reprocessing, Recovery of (6)Ll as Li2CO3.. . . Alvani, C. et al.. . . December 2002. . . ENEA, Rome, Italy; CEA, Gif-sur-Yvette, France.

KEK Proceedings 2002-12. . . Radiation Detectors and Their Uses.. . . Sasaki, S. eds. et al.. . . September 2002. . . KEK, Ibaraki-ken, Japan.

KEK Proceedings 2002-13. . . The 2nd Theory Workshop on JHF Nuclear Physics.. . . Akaishi, Y. eds. et al.. . . July 2002. . . KEK, Tsukuba, Japan.

Nucl. Sci. Eng., 141, 175-189. . . Neutron Spectrum Effects on Burnup, Reactivity, and Isotopics in UO2/H2O Lattices.. . . Xu, Z. et al.. . . July 2002. . . MIT, Cambridge, MA.

Nucl. Sci. Eng., 141, 190-217. . . Object-Oriented Three-Dimensional Fine-Mesh Transport Calculation on Parallel/Distributed Environments for Advanced Reactor Core Analyses.. . . Yamamoto, A., Tatsumi, M.. . . July 2002. . . Nuclear Fuel Industries, Osaka, Japan.

Nucl. Sci. Eng., 141, 218-235. . . A Variational Nodal Expansion Method for the Solution of Multigroup Neutron Diffusion Equations with Heterogeneous Nodes.. . . Tsuiki, M., Hval, S. . . . July 2002. . . Institute for Energy Technology, Halden and Kjeller, Norway.

Nucl. Sci. Eng., 141, 236-251. . . Fully Consistent Diffusion Synthetic Acceleration of Linear Discontinuous SN Transport Discretizations on Unstructured Tetrahedral Meshes.. . . Warsa, J.S. et al.. . . July 2002. . . Los Alamos National Laboratory, Los Alamos, NM.

Nucl. Sci. Eng., 141, 252-271. . . The Evaluation of Radiation Transport Forward-Adjoint Flux Integrals Using Monte Carlo Correlated Coupling Methods.. . . Cramer, S.N.. . . July 2002. . . Oak Ridge National Laboratory, Oak Ridge, TN.

Nucl. Sci. Eng., 141, 272-287. . . Cluster-Event Biasing in Monte Carlo Applications to Systems Reliability.. . . Khazen, M., Dubi, A. . . . July 2002. . . The Technion, Israel Institute of Technology, Haifa, Israel; Ben-Gurion University of the Negev, Beer-Sheva, Israel.

Nucl. Sci. Eng., 143, 99-120. . . Methodology of Continuous-Energy Adjoint Monte Carlo for Neutron, Photon, and Coupled Neutron-Photon Transport.. . . Hoogenboom, J.E.. . . February 2003. . . Delft University of Technology, JB Delft, The Netherlands.

Nucl. Sci. Eng., 143, 121-131. . . Monte Carlo Calculation of Sensitivities to Secondaries' Angular Distributions. . . Perel, R.L.. . . February 2003. . . Hebrew University of Jerusalem, Israel.

Nucl. Sci. Eng., 143, 132-140. . . Sensitivity Analyses for Polyethylene-Moderated and Polyethylene-Reflected Highly Enriched Uranium Experiments Mixed with Waste Matrix Materials.. . . Loaiza, D.J. et al.. . . February 2003. . . Los Alamos National Laboratory, Los Alamos, NM.

Nucl. Sci. Eng., 143, 141-157. . . Optimization of Height-to-Diameter Ratio for an Accelerator-Driven System.. . . Kim. Y. et al.. . . February 2003. . . Korea Atomic Energy Research Institute, Daejeon, Republic of Korea.

Nucl. Sci. Eng., 143, 158-163. . . Statistical Analysis of Reactor Pressure Vessel Fluence Calculation Benchmark Data Using Multiple Regression Techniques.. . . Carew, J.F. et al.. . . February 2003. . . Brookhaven National Laboratory, Upton, NY; State University at Stony Brook, Stony Brook, NY; NRC, Rockville, MD.

Nucl. Sci. Eng., 143, 164-176. . . Combining Intranuclear-Cascade and Preequilibrium Hauser-Feshbach Models for Nuclear Cross-Section Calculations Between 1 MeV and 5 GeV.. . . Fu, C.Y.. Leal, L.C., Guimaraes, F.B. . . . February 2003. . . Oak Ridge National Laboratory, Oak Ridge, TN.

Nucl. Sci. Eng., 143, 177-187. . . Neutron Capture Cross Section of 232Th.. . . Maslov, V.M. et al.. . . February 2003. . . Tohoku University, Sendai, Japan; JAERI, Ibaraki-ken, Japan.

Nucl. Sci. Eng., 143, 188-201. . . A Design Study for 99Tc and 129I Transmutation in the HYPER System.. . . Park, W.S. et al.. . . February 2003. . . Korea Atomic Energy Research Institute, Daejeon, Korea; Seoul National University, Seoul, Korea.

Nucl. Sci. Eng., 143, 202-210. . . Calculation and Analysis of n+ 232Th Reaction Cross Sections.. . . Han, Y. et al.. . . February 2003. . . China Institute of Atomic Energy, Beijing, China; Northwest University, Xi'an, China.

Nucl. Technol., 141, 3-9. . . Modernizing and Maintaining Instrumentation and Control Systems in Nuclear Power Plants.. . . Naser, J. et al.. . . January 2003. . . Electric Power Research Institute, Palo Alto, CA and Charlotte, NC.

Nucl. Technol., 141, 10-32. . . Historical Overview, Current Status, and Future Trends in Human-Computer Interfaces for Process Control.. . . Owre, F.. . . January 2003. . . Organization for Economic Cooperation and Development Halden Reactor Project, Halden, Norway.

Nucl. Technol., 141, 33-44. . . Development of an Advanced Digital Reactor Protection System Using Diverse Dual Processors to Prevent Common-Mode Failure.. . . Shin, H.K. et al.. . . January 2003. . . Korea Power Engineering Co., Daejon, Republic of Korea.

Nucl. Technol., 141, 45-53. . . Development of an Automated Approach to Control System Design.. . . March-Leuba, J., Wood, R.T. . . . January 2003. . . Oak Ridge National Laboratory, Oak Ridge, TN.

Nucl. Technol., 141, 54-62. . . On-Line Monitoring and Dynamic Feature Trending as a Means to Improve In-Service Inspection, Maintenance, and Long-Term Assessment of Systems and Components.. . . Wach, D.H.. . . January 2003. . . Institut fur Sicherheitstechnologie, Garching, Germany.

Nucl. Technol., 141, 63-68. . . Patterns and Intelligent Systems.. . . Cordes, G.A.. . . January 2003. . . Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID.

Nucl. Technol., 141, 69-77. . . Integrating Physical Modeling, Neural Computing, and Statistical Analysis for On-Line Process Monitoring.. . . Garcia, H.E., Vilim, R.B.. . . January 2003. . . Argonne National Laboratory, Idaho Falls, ID.

Nucl. Technol., 141, 78-87. . . Development of Simulation-Based Evaluation System for Iterative Design of Human-Machine Interface in a Nuclear Power Plant - Application for Reducing Workload.. . . Fumizawa, M. et al.. . . January 2003. . . JAERI, Ibaraki-ken, Japan; Nuclear Power Engineering Corp., Tokyo, Japan; Mitsubishi Electric Corp., Hyogo, Japan; Kyoto University, Kyoto, Japan.

Nucl. Technol., 141, 88-107. . . Experimental and Numerical Investigation of Boron Dilution Transients in Pressurized Water Reactors.. . . Hertlein, R.J. et al.. . . January 2003. . . Framatome, Erlangen, Germany; Institute of Safety Research, Dresden, Germany.

Prog. Nucl. Energy, 42, 3-10. . . Effects of Two-Phase Liquid-Gas Flow on the Performance of Nuclear Reactor Cooling Pumps.. . . Poullikkas, A.. . . 2003. . . none noted.

Prog. Nucl. Energy, 42, 11-24. . . Characterization and Extrapolation of a Conceptual Experimental Accelerator Driven System.. . . Kerdraon, D. et al.. . . 2003. . . University of Grenoble, France; Framatome, Lyon, France.

Prog. Nucl. Energy, 42, 25-53. . . Monte Carlo Variance Reduction with Deterministic Importance Functions.. . . Wagner, J.C., Haghighat, A. . . . 2003. . . Penn State University, University Park, PA; Oak Ridge National Laboratory, Oak Ridge, TN.

Prog. Nucl. Energy, 42, 55-106. . . Analytical Benchmark Test Set for Criticality Code Verification.. . . Sood, A. et al.. . . 2003. . . Los Alamos National Laboratory, Los Alamos, NM.

Prog. Nucl. Energy, 42, 107-120. . . Prompt Reactivity Determination in a Subcritical Assembly Through the Response to a Dirac Pulse.. . . Perdu, F. et al.. . . 2003. . . Inst. Sci. Nucl. Grenoble, France.

Prog. Nucl. Energy, 42, 121. . . Simplified P-N and A(n) Methods in Neutron Transport (Vol. 40, 237, 2002).. . . Ciolini, R. et al.. . . 2003. . . University of Pisa, Italy; Politecn Turin, Italy.